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• 2010:08 Development of COLLAGE 3

  The issue of colloid-facilitated radionuclide transport (CFRT) was last addressed by the Swedish nuclear regulators (SKI at that time, now integrated into SSM) in 2001 – 2002. SKI had commissioned the Collage code with subsequent development as Collage 2. This code was employed to investigate the potential role for colloids to have been involved in the transport of radionuclides at the Nevada...

  Content type: Publications

• 2010:17 Quality Assurance Review of SKB’s Copper Corrosion Experiments

  SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...

  Content type: Publications

• 2010:21 Childhood leukaemia around nuclear facilities

  The first indication of a possible relationship between living close to a nuclear installation and the risk of childhood leukaemia came from the United Kingdom in 1983. A cluster of childhood leukaemia in the town of Seascale which is located close to Sellafield was reported in a TV documen-tary. Since then almost 200 studies have been carried out in order to investi-gate the occurrence of...

  Content type: Publications

• 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

  No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...

  Content type: Publications

• 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

  In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...

  Content type: Publications